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| | issue date = 04/20/2018 | | | issue date = 04/20/2018 |
| | title = Review of the Spring 2017 Steam Generator Tube Inspection Report | | | title = Review of the Spring 2017 Steam Generator Tube Inspection Report |
| | author name = Chawla M L | | | author name = Chawla M |
| | author affiliation = NRC/NRR/DORL/LPLIII | | | author affiliation = NRC/NRR/DORL/LPLIII |
| | addressee name = Coffey R | | | addressee name = Coffey R |
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| | docket = 05000301 | | | docket = 05000301 |
| | license number = DPR-027 | | | license number = DPR-027 |
| | contact person = Chawla M L | | | contact person = Chawla M |
| | case reference number = EPID: L-2017-LRO-0033 | | | case reference number = EPID: L-2017-LRO-0033 |
| | document type = Inspection Report, Letter | | | document type = Inspection Report, Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Robert Craven General Plant Manager NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241 April 20, 2018 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 20, 2018 Mr. Robert Craven General Plant Manager NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| POINT BEACH NUCLEAR PLANT, UNIT 2 -REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT (EPID: L-2017-LR0-0033) | | POINT BEACH NUCLEAR PLANT, UNIT 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT (EPID: L-2017-LR0-0033) |
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| ==Dear Mr. Craven:== | | ==Dear Mr. Craven:== |
| By letter dated September 21, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17264A354), NextEra Energy Point Beach LLC (the licensee) submitted information summarizing the results of the Spring 2017 steam generator inspections performed at the Point Beach Nuclear Plant, Unit 2. The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information provided and concludes that the licensee provided the information required by their technical specifications, and that no follow-up is required at this time. The NRC staff's review of the report is enclosed. | | |
| Docket Nos. 50-266 and 50-301 | | By letter dated September 21, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17264A354), NextEra Energy Point Beach LLC (the licensee) submitted information summarizing the results of the Spring 2017 steam generator inspections performed at the Point Beach Nuclear Plant, Unit 2. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information provided and concludes that the licensee provided the information required by their technical specifications, and that no follow-up is required at this time. The NRC staff's review of the report is enclosed. |
| | Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Staff Evaluation cc: ListServ Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation POINT BEACH NUCLEAR PLANT, UNIT 2 REVIEW OF SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT DOCKET NUMBER 50-301 By letter dated September 21, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17264A354), NextEra Energy Point Beach, LLC (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) inspections performed at the Point Beach Nuclear Plant (Point Beach), Unit 2. Point Beach, Unit 2, has two recirculating SGs designed and fabricated by Westinghouse. | | Staff Evaluation cc: ListServ |
| The model Delta 47F SGs were put into service in 1997 during refueling outage (RFO) 22. Each SG has 3,499 thermally treated Alloy 690 tubes that have a nominal 0.875-inch outside diameter and a nominal wall thickness of 0.050 inch. The tubes are arranged in a triangular pattern, were hydraulically expanded at each end for the full depth of the tubesheet. | | |
| The tubesheet is 22.4 inches thick including the cladding. | | POINT BEACH NUCLEAR PLANT, UNIT 2 REVIEW OF SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT DOCKET NUMBER 50-301 By letter dated September 21, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17264A354), NextEra Energy Point Beach, LLC (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) inspections performed at the Point Beach Nuclear Plant (Point Beach), Unit 2. |
| The tubes are supported by a flow distribution baffle, support plates, and anti-vibration bars (AVBs) and are constructed from Type 405 stainless steel. The tube support plates (TSPs) are 1.125 inches thick and have foil shaped holes through which the tubes pass. The U-bend region of the tubes in rows 1 through 14 received a stress relieving thermal treatment after bending. The smallest U-bend radius is 3.25 inches. The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging that was taken in response to the inspection findings. | | Point Beach, Unit 2, has two recirculating SGs designed and fabricated by Westinghouse. The model Delta 47F SGs were put into service in 1997 during refueling outage (RFO) 22. Each SG has 3,499 thermally treated Alloy 690 tubes that have a nominal 0.875- inch outside diameter and a nominal wall thickness of 0.050 inch. The tubes are arranged in a triangular pattern, were hydraulically expanded at each end for the full depth of the tubesheet. The tubesheet is 22.4 inches thick including the cladding. The tubes are supported by a flow distribution baffle, support plates, and anti-vibration bars (AVBs) and are constructed from Type 405 stainless steel. The tube support plates (TSPs) are 1.125 inches thick and have tri-foil shaped holes through which the tubes pass. The U-bend region of the tubes in rows 1 through 14 received a stress relieving thermal treatment after bending. The smallest U-bend radius is 3.25 inches. |
| | The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging that was taken in response to the inspection findings. |
| Based on the review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff has the following observations and comments: | | Based on the review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff has the following observations and comments: |
| * At the completion of Unit 2, Cycle 35, the replacement SGs had accumulated 17.1 Effective Full Power Years (EFPY) and were completed in the second inspection in the second sequential inspection period. | | * At the completion of Unit 2, Cycle 35, the replacement SGs had accumulated 17.1 Effective Full Power Years (EFPY) and were completed in the second inspection in the second sequential inspection period. |
| * The only degradation mechanisms detected were mechanical wear at AVBs and at broached TSPs. No tubes were plugged during RFO 35. No tubes in SG A were plugged and four tubes in SG B were plugged. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. | | * The only degradation mechanisms detected were mechanical wear at AVBs and at broached TSPs. No tubes were plugged during RFO 35. No tubes in SG A were plugged and four tubes in SG B were plugged. |
| In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly and operated units. Enclosure | | Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly and operated units. |
| | Enclosure |
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| ==SUBJECT:== | | ==SUBJECT:== |
| POINT BEACH NUCLEAR PLANT, UNIT 2 -REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT (EPID: L-2017-LR0-0033) | | POINT BEACH NUCLEAR PLANT, UNIT 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT (EPID: L-2017-LR0-0033) |
| DATED APRIL 20, 2018 DISTRIBUTION: | | DATED APRIL 20, 2018 DISTRIBUTION: |
| PUBLIC LPL3 r/f RidsNrrDorlLpl3Resource RidsNrrPMPointBeach Resource RidsOgcRp Resource RidsNsirDpr Resource RidsAcrs_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource RidsNrrLASRohrer Resource Paul Kline, NRR Andrew Johnson, NRR Alan Huynh, NRR ADAMS Accession No.: ML 18095A899 OFFICE D0RL/LPL3/PM D0RL/LPL3/ | | PUBLIC LPL3 r/f RidsNrrDorlLpl3Resource RidsNrrPMPointBeach Resource RidsOgcRp Resource RidsNsirDpr Resource RidsAcrs_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource RidsNrrLASRohrer Resource Paul Kline, NRR Andrew Johnson, NRR Alan Huynh, NRR ADAMS Accession No.: ML18095A899 D0RL/LPL3/ NRR/DMLR/ |
| LA NAME MChawla SRohrer DATE 4/20/18 4/9/18 NRR/DMLR/ | | OFFICE D0RL/LPL3/PM D0RL/LPL3/BC D0RL/LPL3/PM LA MCCB/BC MYoder DWrona NAME MChawla SRohrer MChawla |
| MCCB/BC MYoder /f/SBloom 2/26/18 OFFICIAL RECORD D0RL/LPL3/BC D0RL/LPL3/PM DWrona MChawla 4/20/18 4/20/18}}
| | /f/SBloom DATE 4/20/18 4/9/18 2/26/18 4/20/18 4/20/18 OFFICIAL RECORD}} |
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Category:Inspection Report
MONTHYEARIR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 IR 05000266/20233012023-03-28028 March 2023 NRC Initial Examination Report 05000266/2023301 and 05000301/2023301 IR 05000266/20220062023-03-0101 March 2023 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022006 and 05000301/2022006) IR 05000266/20230102023-02-23023 February 2023 Comprehensive Engineering Team Inspection Report 05000266/2023010 and 05000301/2023010 ML23009B7002023-01-24024 January 2023 Review of the Spring 2022 Steam Generator Tub Inspections Report IR 05000266/20220042023-01-24024 January 2023 Integrated Inspection Report 05000266/2022004 and 05000301/2022004 IR 05000266/20224012022-12-0808 December 2022 Security Baseline Inspection Report 05000266/2022401 and 05000301/2022401 IR 05000266/20224042022-12-0202 December 2022 Cyber Security Inspection Report 05000266/2022404 and 05000301/2022404 IR 05000266/20220032022-11-0707 November 2022 Integrated Inspection Report 05000266/2022003 and 05000301/2022003 ML22298A2972022-10-27027 October 2022 Review of the Fall 2021 Steam Generator Tube Inspections Report IR 05000266/20220122022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000266/2022012 and 05000301/2022012 IR 05000266/20220052022-08-26026 August 2022 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022005 and 05000301/2022005) IR 05000266/20220112022-08-0303 August 2022 Triennial Fire Protection Inspection Report 05000266/2022011 and 05000301/2022011 IR 05000266/20220022022-07-27027 July 2022 Integrated Inspection Report 05000266/2022002 and 05000301/2022002 IR 05000266/20220012022-05-0404 May 2022 Integrated Inspection Report 05000266/2022001 and 05000301/2022001 IR 05000266/20210062022-03-0202 March 2022 Annual Assessment Letter for Point Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021006 and 05000301/2021006) IR 05000266/20220102022-02-0909 February 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000266/2022010 and 05000301/2022010 IR 05000266/20210042022-01-28028 January 2022 Integrated Inspection Report 05000266/2021004 and 05000301/2021004 and Exercise of Enforcement Discretion IR 05000266/20214022021-11-10010 November 2021 Security Baseline Inspection Report 05000266/2021402 and 05000301/2021402 IR 05000266/20210032021-10-20020 October 2021 Integrated Inspection Report 05000266/2021003 and 05000301/2021003 IR 05000266/20215012021-10-0505 October 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2021501 and 05000301/2021501 IR 05000266/20213012021-09-14014 September 2021 NRC Initial License Examination Report 05000266/2021301; 05000301/2021301, and 07200005/2021301 IR 05000266/20210052021-09-0101 September 2021 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021005 and 05000301/2021005) IR 05000266/20214032021-08-0404 August 2021 Security Baseline Inspection Report 05000266/2021403 and 05000301/2021403 IR 05000266/20210022021-07-29029 July 2021 Integrated Inspection Report 05000266/2021002, 05000301/2021002, and 07200005/2021001 IR 05000266/20210102021-07-0101 July 2021 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000266/2021010 and 05000301/2021010 IR 05000266/20210012021-04-21021 April 2021 Integrated Inspection Report 05000266/2021001 and 05000301/2021001 IR 05000266/20214012021-03-16016 March 2021 Security Baseline Inspection Report 05000266/2021401; 05000301/2021401; Independent Spent Fuel Storage Security Inspection Report 07200005/2021401 IR 05000266/20200062021-03-0404 March 2021 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020006 and 05000301/2020006) IR 05000266/20200902021-02-0909 February 2021 Final Significance Determination of a Green Finding; NRC Inspection Report 05000266/2020090 and 05000301/2020090 IR 05000266/20200042021-02-0808 February 2021 Integrated Inspection Report 05000266/2020004 and 05000301/2020004 IR 05000266/20204022020-12-14014 December 2020 Security Baseline Inspection Report 05000266/2020402 and 05000301/2020402 IR 05000266/20200032020-11-0404 November 2020 Integrated Inspection Report 05000266/2020003 and 05000301/2020003 IR 05000266/20200102020-09-24024 September 2020 Biennial Problem Identification and Resolution Inspection Report 05000266/2020010 and 05000301/2020010 IR 05000266/20200052020-09-0101 September 2020 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020005 and 05000301/2020005) IR 05000266/20200022020-08-0606 August 2020 Integrated Inspection Report 05000266/2020002 and 05000301/2020002 IR 05000266/20200122020-08-0303 August 2020 NRC Inspection Report 05000266/2020012 and 05000301/2020012; Preliminary White Finding and Apparent Violations IR 05000266/20200112020-07-29029 July 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000266/2020011 and 05000301/2020011 IR 05000266/20200012020-05-13013 May 2020 Integrated Inspection Report 05000266/2020001 and 05000301/2020001 ML20100G8902020-04-0707 April 2020 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000266/2020-011 and 05000301/2020-011 IR 05000266/20204012020-03-30030 March 2020 Security Baseline Inspection Report 05000266/2020401 and 05000301/2020401 IR 05000266/20190062020-03-0303 March 2020 Annual Assessment Letter for Point Beach Nuclear Plants, Units 1 and 2 (Report 05000266/2019006 and 05000301/2019006) IR 05000266/20190042020-02-0505 February 2020 Integrated Inspection Report 05000266/2019004 and 05000301/2019004 2024-02-01
[Table view] Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 20, 2018 Mr. Robert Craven General Plant Manager NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT (EPID: L-2017-LR0-0033)
Dear Mr. Craven:
By letter dated September 21, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17264A354), NextEra Energy Point Beach LLC (the licensee) submitted information summarizing the results of the Spring 2017 steam generator inspections performed at the Point Beach Nuclear Plant, Unit 2.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information provided and concludes that the licensee provided the information required by their technical specifications, and that no follow-up is required at this time. The NRC staff's review of the report is enclosed.
Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Staff Evaluation cc: ListServ
POINT BEACH NUCLEAR PLANT, UNIT 2 REVIEW OF SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT DOCKET NUMBER 50-301 By letter dated September 21, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17264A354), NextEra Energy Point Beach, LLC (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) inspections performed at the Point Beach Nuclear Plant (Point Beach), Unit 2.
Point Beach, Unit 2, has two recirculating SGs designed and fabricated by Westinghouse. The model Delta 47F SGs were put into service in 1997 during refueling outage (RFO) 22. Each SG has 3,499 thermally treated Alloy 690 tubes that have a nominal 0.875- inch outside diameter and a nominal wall thickness of 0.050 inch. The tubes are arranged in a triangular pattern, were hydraulically expanded at each end for the full depth of the tubesheet. The tubesheet is 22.4 inches thick including the cladding. The tubes are supported by a flow distribution baffle, support plates, and anti-vibration bars (AVBs) and are constructed from Type 405 stainless steel. The tube support plates (TSPs) are 1.125 inches thick and have tri-foil shaped holes through which the tubes pass. The U-bend region of the tubes in rows 1 through 14 received a stress relieving thermal treatment after bending. The smallest U-bend radius is 3.25 inches.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging that was taken in response to the inspection findings.
Based on the review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff has the following observations and comments:
- At the completion of Unit 2, Cycle 35, the replacement SGs had accumulated 17.1 Effective Full Power Years (EFPY) and were completed in the second inspection in the second sequential inspection period.
- The only degradation mechanisms detected were mechanical wear at AVBs and at broached TSPs. No tubes were plugged during RFO 35. No tubes in SG A were plugged and four tubes in SG B were plugged.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly and operated units.
Enclosure
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSPECTION REPORT (EPID: L-2017-LR0-0033)
DATED APRIL 20, 2018 DISTRIBUTION:
PUBLIC LPL3 r/f RidsNrrDorlLpl3Resource RidsNrrPMPointBeach Resource RidsOgcRp Resource RidsNsirDpr Resource RidsAcrs_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource RidsNrrLASRohrer Resource Paul Kline, NRR Andrew Johnson, NRR Alan Huynh, NRR ADAMS Accession No.: ML18095A899 D0RL/LPL3/ NRR/DMLR/
OFFICE D0RL/LPL3/PM D0RL/LPL3/BC D0RL/LPL3/PM LA MCCB/BC MYoder DWrona NAME MChawla SRohrer MChawla
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